School of Nuclear Engineering

Purdue University

West Lafayette, IN 47907-1290

 

NUCL 351 Nuclear Thermal Hydraulics – II

(Heat Transfer)

Spring 2003

 

Instructor:                  Professor S. T. Revankar      

Office: NUCL 132E, Phone: 496-1782

Office Hours:             8:30 am-10:30 am –  Thursday or by appointment

 

Class Room:              GRIS 160, MWF 8:30-9:20am

 

Text:                           "Fundamentals of Heat and Mass Transfer,” Fifth Edition, Frank P.

  Incropera and David P. DeWitt, John Wiley & Sons Inc. (2000)

 

Attendance:               Since class discussion is a major course ingredient, regular attendance is

mandatory. Attendance record will be taken into consideration in any borderline grade decisions.

 

Homework:                Homework will be assigned at least one week in advance and will be due at the beginning of the Monday class period, unless specified otherwise. All handwritten homework will be completed on engineering quadrille paper using the attached sample format. The work must be legible, neat, and in HB pencil. Be sure that your name, date, set number, and appropriate page number, in accordance with the attached format, are included on all sheets. Computer output is acceptable for programs, numeric output, and graphical results. Homework may be completed using MATHCAD or other such software. When such tools are used the problem statement, assumptions, and solution approach should be organized in a manner similar to the hand written example attached.

 

Design Project:         A heat transfer system design problem will be assigned to a each team made of 3-4 students after the first hour exam and each team members will be expected to orally present and produce a complete engineering report documenting the team work on this project. The format and further instructions for the project will be provided when the problem is assigned. The report will be due the last day of class before finals week.

 

Homework and the Design Project report will be graded based on neatness and format (10%), clarity of presentation (20%), correctness of approach (50%), right answer or reasonable conclusions (20%).

 

Course Grading:       Hour exams (2)                       40%

                                    Homework                              25%

                                    Design Project                                    10%

                                    Final exam                              25%

 

Final Grade Scale:    A = 85-100; B = 75-84; C = 65-74; D = 55-64; F < 55          

 


 

Click here for The Class Schedule

 

Click here for  CLASS NOTES

Please Note that  the HW problems have been updated 

 

Click here for 


 

 

School of Nuclear Engineering

Purdue University

West Lafayette, IN 47907-1290

 

NUCL 351 Nuclear Thermal-Hydraulics II

(Heat Transfer)

Spring  2003

 

REFERENCE LIST

 

Reference List on Heat Transfer

 

 

 

1.      Holman J.P., “Heat Transfer”, 8th Edition, McGraw-Hill 1997.

2.      Pitts D. R. and Sissom L.E., “Heat Transfer” Schaum’s Outline Series in Engineering, McGraw-Hill 1977.

3.      Lienhard J.H., “A Heat Transfer Textbook” Prentice-Hall, 1981.

4.      Kays, W.M., “Convective Heat and Mass Transfer,” McGraw-Hill 1966.

5.      Eckert E.R.G., and Drake R.M., “analysis of Heat and Mass Transfer”,  McGraw-Hill 1972.

6.      Hagan K.D., “Heat Transfer with Applications”, Prentice Hall, 1999.

7.      Cengel Yunus A., “Heat Transfer A Practicle Approach” McGraw-Hill 1998.

8.      Mills A.F., “Basic Heat and Mass Transfer” , Prentice Hall, 1999

 

 

Two-Phase Heat Transfer & Reactor Thermalhydraulics

 

 

1.      Lahey, R.T. and Moody, F.J., "The Thermal-Hydraulics of a Boiling Water Nuclear Reactor," American Nuclear Society, 1977.

2.      Tong L.S. and Weisman J., “Thermal Analysis of Pressurized Water Reactors”, American Nuclear Society, 1970.

3.      Delhaye, J.M., Giot, M., Riethmuller, M.L., "Thermohydraulics of Two-Phase Systems for Industrial Design and Nuclear Engineering," Hemisphere Publishing Corporation, McGraw-Hill, 1981.

4.      Ginoux J.J “Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems”, Hemisphere Publishing Corp., 1978.